Many additions to CRPG presentations.

presentations/crpg_2011-10-06/annulus.tex

@@ -0,0 +1,13 @@
+\begin{figure}
+\begin{center}
+\begin{tikzpicture}
+[
+  transform canvas = {scale=1.0},
+]
+
+\fill[mitred] (0,0) circle (1cm);
+\fill[white]  (0,0) circle (0.50cm);
+
+\end{tikzpicture}
+\end{center}
+\end{figure}

presentations/crpg_2011-10-06/graphical_settings.tex

@@ -12,7 +12,7 @@
 [
 	draw,
 	rectangle,
-	fill			= blue!20,
+	fill			= blue!50,
 	minimum height	= 2em,
 	minimum width	= 2em,
 ]
@@ -21,7 +21,7 @@
 [
 	draw,
 	rectangle,
-	fill			= green!20,
+	fill			= green!75,
 	minimum height	= 2em,
 	minimum width	= 2em,
 ]

presentations/crpg_2011-10-06/slides.tex

@@ -17,7 +17,7 @@
 
 \title{The OpenMC Monte Carlo Code}
 \author{Paul K. Romano}
-\date{September 30, 2011}
+\date{October 6, 2011}
 \pgfdeclareimage[height=0.5cm]{mit-logo}{mit-logo.pdf}
 \logo{\pgfuseimage{mit-logo}\hspace*{0.3cm}}
 
@@ -72,16 +72,46 @@
   \end{itemize}
 \end{frame}
 
+\begin{frame}{Monte Carlo}
+  Rather than solving the transport equation by discretizing the spatial,
+  energy, and angular variables, Monte Carlo solves the transport equation by
+  following individual particles as they move stochastically through a medium.
+  \begin{itemize}
+  \item<1-> Standard deviation $\propto \frac{1}{\sqrt{N}}$
+  \end{itemize}
+\end{frame}
+
 % -----------------------------------------------------------------------------
 \section{Methods and Theory}
 
+\begin{frame}{Solution Algorithm}
+  \begin{itemize}
+  \item<1-> Loop over particles
+    \begin{enumerate}
+    \item<1-> Sample particle from distribution
+    \item<1-> Track particle to next collision
+    \item<1-> Sample nuclide within material
+    \item<1-> Sample reaction within nuclide
+    \item<1-> Repeat from step 2 until particle dies
+    \end{enumerate}
+  \end{itemize}
+
+  While particle is being tracked, keep track of collision rate, fission rate,
+  etc.
+  \begin{equation*}
+    \phi = \frac{1}{NV} \sum\limits_{\text{all collisions} \atop \text{in cell}} \frac{w_i}{\Sigma_t (E_i)}
+  \end{equation*}
+
+\end{frame}
+
 \begin{frame}{Geometry}
   \begin{itemize}
   \item<1-> All geometry is described as constructive solid geometry (unions and
     intersections of second-order surfaces)
+  \item<1-> $Ax^2 + By^2 + Cz^2 + Dxy + Eyz + Fxz + Gx + Hy + Iz + J = 0$
   \item<1-> e.g. to construct an annulus
   \end{itemize}
-  % Picture of annulus
+  \include{annulus}
 \end{frame}
 
 \begin{frame}{Cross-Sections}
@@ -100,13 +130,22 @@
 \begin{frame}{Union Energy Grid}
   \begin{itemize}
   \item<1-> Each nuclide has cross-sections tabulated at different energy points
-  \item<1-> To determine collision type, need $\Sigma$ for each collision
+  \item<1-> To determine collision type, need to look up microscopic reaction
+    cross sections
   \end{itemize}
   \include{union_energy_grid}
-
 \end{frame}
 
-\begin{frame}{Tallies}
+\begin{frame}{Tallies}{}
+  {\bf Remember:} In Monte Carlo, the only answer you get is the one you ask
+  for. In general, you don't get the global solution like you do in
+  deterministic land.
+  \begin{itemize}
+  \item<1-> Implemented a robust tally system to calculate user-specified
+    quantities of interest
+  \item<1-> {\bf Filters:} Spatial location, incoming/outgoing energy, birth region, mesh
+  \item<1-> {\bf Responses:} Flux, reaction rates, currents, etc.
+  \end{itemize}
 \end{frame}
 
 \begin{frame}{Parallel Fission Bank}
@@ -119,6 +158,13 @@
 \end{frame}
 
 \begin{frame}{XML Input Format}
+  Unlike many nuclear codes, OpenMC uses a modular XML input format
+  \begin{itemize}
+  \item<1-> Building a geometric model -- {\bf geometry.xml}
+  \item<1-> Assigning materials to volumes -- {\bf materials.xml}
+  \item<1-> Setting parameters for the simulation -- {\bf settings.xml}
+  \item<1-> Determining which quantities to score -- {\bf tallies.xml}
+  \end{itemize}
 \end{frame}
 
 \begin{frame}{Running}

presentations/crpg_2011-10-06/union_energy_grid.tex

@@ -7,7 +7,10 @@
   yshift = 1.0cm
 ]
 
-  \node (LabelOne)  [sTextBlockStyle]                      {Union Energy Grid};
+  \node (LabelOne)   [sTextBlockStyle]                      {Union Energy Grid};
+  \node (LabelTwo)   [sTextBlockStyle, below of = LabelOne, node distance = 1.5cm] {Nuclide Pointers};
+  \node (LabelThree) [sTextBlockStyle, below of = LabelTwo, node distance = 1.5cm] {Nuclide Energy Grid};
+
   \node (EOne)      [RectBlue, right of = LabelOne, node distance = 3cm] {$E_1$};
   \node (ETwo)      [RectBlue, right of = EOne]   {$E_2$};
   \node (EThree)    [RectBlue, right of = ETwo]   {$E_3$};
@@ -39,6 +42,9 @@
   \draw [-triangle 45, thick] (ESeven) -- (PSeven);
   \draw [-triangle 45, thick] (EEight) -- (PEight);
 
+  \draw [dashed] (-2,-0.70) -- (10.5,-0.70);
+  \draw [dashed] (-2,-2.20) -- (10.5,-2.20);
+
 \end{tikzpicture}
 \end{center}
 \end{figure}